ML20247D670
| ML20247D670 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/18/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0800, RTR-NUREG-800 NLS-89-147, NUDOCS 8905250540 | |
| Download: ML20247D670 (3) | |
Text
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- l Carolina Power & Light Company
- MAYi 81989 United States Nuclear Regulatory Commission ATTENTION: l Document Control Desk Washington,,DC' 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2' DOCKET. NOS. 50-325 ' & 50-324/ LICENSE NOS. DPR-71. & DPR-62 REVISION TO A PRIOR COMMITMENT FIRE DOOR SUPERVISION Gentlemen:
By letter dated June 23, 1977, Carolina Power & Light Company (CP&L) committed to lock or alarm certain fire doors protecting safety-related areas. These doors were located in low personnel traffic areas. The intent of this commitment was to assure that fire doors were maintained in the ulosed position.
Compliance with this commitment was accomplished with the use of the plant security. system. However, as a result of changes in security-requirements, over-utilization of the security computer necessitated removal of the. fire door. supervision function.
-NUREG-0800, Revision 2, July 1981, Section 9.5.1.C.S.a(5) identifies acceptable measures that could be provided to ensure that fire doors will be effective in the event of.a fire. As such, CP&L has reevaluated the method of fire door supervision for these 67 doors and has instituted a daily inspection to verify their position. This verification is performed by Operations.
Plant Security patrols these areas'several times daily and, although not responsible for fire door status, is aware of the importance of fire doors.
The importance of fire doors being maintained in a closed position is emphasized during site employee training.
With the implementation of the surveillance described above, CP&L has determined that removal of.the supervisory alarm system for the fire doors does not create a safety concern.
Please refer any questions regarding this submittal to Mr. Stephen D. Floyd at (919) 546-6901.
Y urs very truly,
'8905250540 890518 Pl PDR ADOCK 050003243.
F PNUf' L.
. L flin Man er Nuclear Lice sing Section DBB/crs (336CRS) cc:
Mr. S. D. Ebneter Mr. k. H. Ruland Mr. E. G. Tourigny h
411 Fayetteville Street e P. O. Box 1551
- Raleigh. ft C. 27602 I
s i
'I%BLE 5 ADDm DUM l
Effluent ard Waste Disposal pianrnial Report 1988 Year Gaseous Effluents - Grourd IcVel Beleases 3/4 Quarters Continuous Mode Batch tbde I
i I
i Nuclides Released Unit l
Quarter 3
! Quarter 4 l
Quarter 3
! Quarter 4 3.
Particulate I
Strontium-89 Ci (1)
- 0. 00E+00 (2)
N/A N/A Strontium-90 Ci (1) l 0.00E+00(2)
N/A N/A l
l I
l I
Total for Period l
Ci l
(1) l 1.43E-06 l
N/A l
N/A (1) - Previously Reported (2) Quarterly cmposite particulate filter analysis indicates a Minimum Detectable Activity (MDA) concentration of <5 E-16 uCi/cc for the Fuel Building Exhaust Vent and the Radwaste Building Exhaust Vent.
This value is less than the Lower Limit of
-11 Detection (LLD) of 1 x 10 uCi/ml as specified in table 4.11.2.1.2-1 of RBS Technical Specifications.
4 o
- e S HLE 6 ADDEMIM Effluent and Waste Diammal h4=rwn=1 Report 1988 har G.
Tir=iid Effluent 3/4 Quarters continuous Mode Batch Mode i
Nuclides Released Unit Ouarter 3 Quarter 4 Quarter 3 Ouarter 4 Strontium-89
'Ci N/A N/A (1)
- 0. 00E+00 (2)
Strontium-90 Ci N/A N/A (1)-
0.00E+00 (2) i Iron-55 Ci N/A N/A (1) 4.50E-03 Total For Period Ci N/A N/A (1) l 4.64E+00 (1) - Previously Reported
'(2) Analysis of. quarterly ccuposite indicates a Minimum Detectable
- Activity (MDA) concentration of <2.0 E-08 uCi/ml.
These values
~0 are 'less than the Lower Limit of Detection (ILD) of 5 x'10 uCi/ml as specified' in Table 4.11.1.1.1-1 of RBS Technical Specifications.
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